ML19317D519

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Responds to NRC 760608 Request for Schedule Re Util Response to Reactor Vessel Support Sys Questions.Study Re Probability of Failure of Reactor Coolant Sys in Annular Region Between Reactor Vessel & Cavity Shield Wall to Be Ready Dec 1976
ML19317D519
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 09/14/1976
From: Parker W
DUKE POWER CO.
To: Rusche B
Office of Nuclear Reactor Regulation
References
NUDOCS 7912060775
Download: ML19317D519 (1)


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Mr. Benard C. Rusche

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ot Attention:

Mr. A. Schwencer, Chief

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Operating Reactors Branch #1

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Oconee Nuclear Station 6

Docket Nos. 50-269, -270, -287

Dear Mr. Rusche:

Your letter of June 8, 1976 requested that a schedule be submitted concerning our response to questions relative to the Oconee Nuclear Station reactor vessel support system.

Subsequently, in our August 13, 1976 letter, it was stated that a users group of utilities that have Babcock and Wilcox 177 FA Nuclear Steam Supply Systems had been formed to develop plans and schedules for resolution of this concern.

Duke Power Company, in conjunction with this users group and several consultants, has reviewed the probability study which was developed by the Combustion Engineering users group and presented to the NRC staff.

Based on this study, and other information currently available, we believe the probability of the occurrence of the particular inci-dent of concern is acceptably remote and no further analysis is necessary.

In order to evaluate and quantify this probability, we are having a study performed of the probability of a failure of the reactor coolant system in the annular region between the reactor vessel and the cavity shield wall.

We expect this study to be completed by mid December, 1976, and will at that time discuss the results with your staff.

O Ve truly yours,j h we lb.

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- William O. Parker, Jr. g MST:vr 35ou 7912060776 a